Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Yu. Vorobyov"'
Publikováno v:
Nuclear and Radiation Safety. :5-12
One of the key aspects for safety assessment of spent fuel dry storage systems is evaluation of the temperature profile for spent fuel in various storage conditions. In this effort, a three-dimensional model of a vertical dry storage HI‑STORM 190 U
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5779539f19dcfcc820639ce2834d512c
https://doi.org/10.32918/nrs.2022.4(96).01
https://doi.org/10.32918/nrs.2022.4(96).01
Publikováno v:
Lobachevskii Journal of Mathematics. 42:2571-2579
When solving complex problems of numerical modeling, computational meshes, containing hundreds millions of cells are quite often. Modern tasks even cross the line of billion cells. Workstations are unable to cope with such volume of data and computat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::abfe0df1a46f2bfe303d8dd8edf5d718
https://doi.org/10.1134/s1995080221110202
https://doi.org/10.1134/s1995080221110202
Publikováno v:
Nuclear and Radiation Safety. :30-40
An overview of the main improvements in updated version 2.1 of MELCOR computer code related to more representative mathematical modeling of complex thermohydraulic severe accident processes of core degradation, transfer of molten fragments to the bot
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b7f6f03387ced9627be75b85997ca151
https://doi.org/10.32918/nrs.2020.1(85).03
https://doi.org/10.32918/nrs.2020.1(85).03
Autor:
T. Hollands, M. Stempniewicz, M. Barnak, P. Vokac, D. Angelova, M. Behler, R. Dagan, Claudia López, Algirdas Kaliatka, G.L. Horvath, D.F. Da Cruz, Ivo Kljenak, P. Matejovic, B.S. Jäckel, O. Kotsuba, Giacomino Bandini, M. Matkovic, Martin Steinbrück, Yu. Vorobyov, Luis E. Herranz, V. Vileiniskis, F. Rocchi, O. Zhabin, Olivia Coindreau, R. Thomas, D.C. Visser, F. Alcaro, Terttaliisa Lind, K. Mancheva, S. Ederli, P. Drai
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 120, pp.880-887. ⟨10.1016/j.anucene.2018.06.043⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, 120, pp.880-887. ⟨10.1016/j.anucene.2018.06.043⟩
International audience; Spent fuel pools (SFPs) are large structures equipped with storage racks designed to temporarily storeirradiated nuclear fuel removed from the reactor. SFP severe accidents have long been considered ashighly improbable since t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1a141d57553ae7b281b6f0a491fb6d3e
https://doi.org/10.1016/j.anucene.2018.06.043
https://doi.org/10.1016/j.anucene.2018.06.043
Publikováno v:
Nuclear and Radiation Safety. :20-23
This paper evaluates the thermohydraulic aspects of modeling multi-purpose container (MPC-31) with VVER-1000 spent nuclear fuel (SNF) during its long-term storage in HI-STORM container (designed by Holtec International). The paper describes the main
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::20917b9942d93b565eb1fc28af78bb94
https://doi.org/10.32918/nrs.2017.2(74).04
https://doi.org/10.32918/nrs.2017.2(74).04
Publikováno v:
Вісник Харківського національного автомобільно-дорожнього університету; № 85 (2019); 83
Bulletin of Kharkov National Automobile and Highway University; № 85 (2019); 83
Вестник Харьковского национального автомобильно-дорожного университета; № 85 (2019); 83
Bulletin of Kharkov National Automobile and Highway University; № 85 (2019); 83
Вестник Харьковского национального автомобильно-дорожного университета; № 85 (2019); 83
Розглянуто питання щодо принципів вибору основних показників поршневого пневмодвигуна гібридної силової установки «ДВЗ-пневмодвигун
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::32b8bfd79199a582dbc55ec48e678825
http://bulletin.khadi.kharkov.ua/article/view/179542
http://bulletin.khadi.kharkov.ua/article/view/179542
Publikováno v:
Nuclear and Radiation Safety. :13-20
The paper presents specific approaches to modeling the spent fuel pool (SFP) of Fukushima Daiichi NPP and results of thermohydraulic calculations of severe accidents in SFP using MELCOR 1.8.6 computer code. The dynamics of main processes accompanying
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::16034a97e6d17cfa40308cccaccdc336
https://doi.org/10.32918/nrs.2016.4(72).02
https://doi.org/10.32918/nrs.2016.4(72).02
Publikováno v:
Nuclear and Radiation Safety. :19-22
The paper presents applicability of built-in RELAP5/MOD3.2 cladding deformation model for VVER-1000 fuel with cladding of Zr+1 % Nb alloy. Experimental data and simplified model of fuel assembly channel of the core are used for this purpose. The mode
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::25ec635134f22ced2c5b6809dc452527
https://doi.org/10.32918/nrs.2016.3(71).04
https://doi.org/10.32918/nrs.2016.3(71).04